ML20070Q521

Nuclear Power Plant Sys Sourcebook,Fort Calhoun

ML20070Q521
Person / Time
Site:	Fort Calhoun
Issue date:	12/31/1988
From:	Horton W, Lobner P SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY
To:	NRC
References
CON-FIN-D-1763, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-88-1982, NUDOCS 9103290108
Download: ML20070Q521 (82)

Text

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i SAIC 88/1982 l 4p y NUCLEAR POWER PLANT n i SYSTEM SOURCEBOOK t A / 44**M l FT. CALHOUN 50 283 O l Editor: Peter Lobner i Author: William liorton l l Prepared for: U.S. Nuclear Regulatory Commission Washington,- D.C. 20555 Contract NRC 03 87 029 l FIN D 1763

Fon Calhoun ' TABLE OF CONTENTS Sectmn P.ags 1 S UMMARY D ATA ON PLANT............................................ I 2 IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS... 1 3 SYSTEM INFORMATION.................................................. 2 3.1 Reac tor Coolant S yste m (RCS)................................ 7-3.2 Auxiliary Feedwater(AFW) System and Secondary S team Relle f (S S R) System................................... 12 3,3 S afety Injection System (S1S)................................. 18 3.4 Containment Spray (CS) System.............................. 24 3.5 Electric Power Syste m.......................................... 29 3.6 Auxiliary Coolant Component Cooling Water S ys te m (CCW)................................................... 38 3.7 Raw Water (RW) S ystem...................................... 45 3.8 Containment Air Cooling (CAC) System..................... 52 3.9 Instrumentation and Contml (I&C) Systems................. '55 4 PLANT INFORMATION.................................................... 58 4.1 Site and B uildin g S ummary.................................... 58 g 4.2 Facility Layout Drawin 58 Section 4 References..gs....................................... 4.3

58 5

BIBLIOGRAPHY FOR FORT CALHOUN POWER STATION...... 75 i .1 i 12/88 -+ee-, y v .w., ,me,-__ce r,m-- .,,,,~,.Awnwi,-%eo--,--,r-,r w-r.,-n-,rww .--1,.-en v. ve, m.,+m ..er. e,m..

-.. - ~ - - -... - -.. - -. - Fort Calhoun LIST OF FIGURES EigEt fast 31 Cooling Water Systems Functional Diagram for Fort Calhoun............ 6 3.1-1 Fort Calhoun Reactor Coolant System...................................., 9 3.1-2 Fort Calhoun Reactor Coolant System Showing Component Locations. 10 3.2 1 Fort Calhoun Auxiliary Feedwater and Secondary Steam Relief Systems.........................................................................15 3.2 2 Fort Calhoun Auxiliary Feedwater and Secondar Systems Showing Component locations........y Steam Relief ...........................16 3.3 1 Fort Calhoun High Presstue Safety Injection System..................... 21 3.3 2 Fort Calhoun High Pressure Safety Injection System S howing Component Locations.............................................. 22 3,4-1 Fort Calhoun Containment S pray System.................................. 26 3.4 2 Fort Calhoun Containment Spray System Showing Component loc a tion s....................................................................... 27 - 0 s 3.5 1 Fort Calhoun 4160 and 480 VAC Electric Power Distribution System. 31 3.5 2 Fort Calhoun 125VDC and 125 VAC Electric Power Distribution....... 32 3.6 1 Fort Calhoun Auxiliary Coolant Component Cooling Water System.... -40 i 3.6 2 Fort Calhoun Auxiliary Coolant Com Showing Component Locations.....ponent Cooling Water System L ........................................42 I 3.71 Fon Calhoun Raw Water System............................................ 47 3.7 2 Fort Calhoun Raw Water System Showing Component locatio.is...... 49 41 General View of Fort Calhoun Site and Vicinity............................ - 59 l 42 Fort Calh o u n Plo t Pl a n........................................................ 60 4-3 Fort Calhoun Auxiliary Buildin (Elevation 97l')..................g& Containment Sub basement ..............................................61 44 Fort Calhoun Auxiliar - (Elevation 989')......y Building & Containment Basement ...........................................................62 45 Fcrt Calhoun Auxiliary Building & Containment Ground Floor (Elevation 1007')...............................................................63 ii 12/88

Fort Calhoun LIST OF-FIGURES (Continued) Figure hgg 46 Fort Calhoun Auxiliary Building & Containment Intermediate Floor (Elevation 1025')...............................................................64 47 Fort Calhoun Auxiliary Building & Containment Operating Floor (Elevation 1036')...............................................................65 48 Fon Calhoun Auxiliary Building & Containment (Elevation 1057')..............................................................66 49 Fort Calhoun Intake S tructure................................................ 67.- l I 1 iii 12/88 -.--. = -.

Fon Calhoun LIST OF TABLES 1 OV na em 31 Summary of Fon Calhoun Systems Covered in this Repon.............. 3 3.1 1 Fon Calhoun Reactor Coolant System Data Summary for S e le c t ed Compo nents.......................................................... I1 3.2 1 Fon Calhoun Auxiliary Feedwater System Data Summary for Selected Componen ts...................................................... 17 3.3-1 Fort Calhoun High Pressure Safety Injection System Data S u mmary for S elec ted Compon e n t s.......................................... 23-3.4 1 Fon Calhoun Containment Spray System Data Summary for Selected Components...................................................... 28 3.5 1 Fon Calhoun Electric Power System Data Summary for S elec ted Compone nts.......................................................... 33 3.5 2 Partial Lising of Electrical Sources and Loads at Fort Calhoun.......... 35 3.6-1 Fon Calhoun Auxiliary Coolant Component Cooling Water System Data Summary for Selected Components.......................... 44 3.7-1 Fort Calhoun Raw Water System Data Summary for Selected 'l Components..................................................................... 51 J 3.8 1 Fon Calhoun Containment Air Cooling System Data Summary for Selected Components...................................................... 54 4-1 Definition for Fort Calhoun Building and Location Codes................ 68 4-2 Panial Listing of Components by Location at Fon Calhoun.............. 69 d iv 12/88

l Fort Calhoun l-i t NOTICE - t. This sourcebook will be periodically updated with new and/or replacement i pages as appropriate to incorporate additional information on this reactor plant. Techmcal errors in this report should be brought to the attention of I the following: Mr. Peter Lobner i Manager, Systems Engineering Division i Science ApplicationsInternationalCorporation 10210 Campus Point Drive San Diego,CA 92131 (619) 458-2673 Correction and other recommended changes should be submitted in the form j of marked up copies of the affected text, tables or figures Supporting i documentation should be included if possible, i 1 a 1 4 i e i l I [ . 12/88 v. i- 'ee-r ,-,v-, w -....wy e.,,,,,,,wweq., .m.*, ,--w .w. ,-m.. e,,--w.,...w.e.,, ,w,-.,..-,

FORT CALHOUN RECORD OF REVISIONS J q i REVISION ISSUE COMMENTS 0 12/88 Original report i 3 a \\ 4 p l l i 5 i l a vi. 12/88 i -e +- -.-s. s,--. e e e ,w....,., w.,w,.y. , r #m y ,-w--, ,.w., v'

Fort Calhoun i FORT CALIIOUN SYSTEM SOURCEBOOK This sourcebook contains summary information on the Fort Calhoun Station, t Unit No.1. Summary data on this plant are presented in Section 1, and similar nuclear power plants are identified in Section 2. Information on selected reactor plant systems is presented in Section 3, and the site and building layout is illustrated in Section 4. A e bibliography of reports that describe features of this plant or site is presented in Section 5. 1.

SUMMARY

DATA ON PLANT Basic information on the Fort Calhoun Station, Unit No. I nuclear power plant is li;ted below: Docket number 50 285 Operator Omaha Public Power District Location Nebraska,19 miles north of Omaha Commercial operation date 9#3 Reactor type PWR NSSS vendor Combustion Engineering Number ofloops 2 Power (MWt/MWe) 1420/457 Architect-engineer Gibbs, Hill, Durham, and Richardson, Inc. Containment type Reinforced concrete cylinder with steel liner, post tensioned in three directions 2. IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS The Fort Calhoun is an early vintage Combustion Engineering PWR with a two loo? nuclear steam supply system (NSSS). In terms of power rating, Fort Calhoun is the sma Llest operating C-E plant. Other two-loop Combustion Engineering plants in the United States are: Arkansas Nuclear One -2 Calven Cliffs 1 and 2 4 Millstone 2 4 Palisades Palo Verde 1,2, and 3 San Onofre 2 and 3 ) St. Lucie 1 and 2 ~ Waterford3 All of these plants have large, dry containments. b J ( l 12/88 L-4

Fort Calhoun 3. SYSTEM INFORMATION This section contains descriptions of selected systems at the Fort Calhoun Station in terms of general function, operation, system success criteria, major components, and support system requirements. A summary of major systems at the Fort Calhoun Station is presented in Table 31. In the "Re port Section" column of this table, a section reference (i.e. 3.1,3.2, etc.) is provided for al; systems that are described in this report. An entry of "X" in this column means that the system is not described in this report. In the "FSAR Section Reference" column, a cross reference is provided to the section of the Final Safety Analysis Report where additional information on each system can be found. Other sources of information on this plant are identified in the bibliography in Section 5. Several cooling water systems are iderdified m Table 31. The functional - relationships that exist among coolin;; water systems required for safe shutdown are shown in Figure 31. Details on the indivic ual cooling. water systems are provided in the report secuons identified in Table 31. l l t 2 12/88 o- .c-- ,,,,.........-.,.--._-y-m_,_.., ym.w,..,%_,.,%., -,m,y,.%,.y.-,.

Table 3-1. Summary of Fort Calhoun Systems Covered in this Report Generic Plant-Specific Report FSAR Section System Name System Name Section Reference Reactor Heat Removal Systems - ' Reactor Coolant System (RCS) Same 3.1 4 l - Auxiliary Feedwater(AFW)and - Same 3.2 9.4 Secondary Steam Relief (SSR) Systems Emergency Core Cooling Systems Safety Injection System (SIS) (ECCS) - High-Pressure Injection High-Pressure Safety 3.3 6.2 & Recirculation Injection System - Low-pressure Injection - Low-Pressure Safety X 6.2 & Recirculation Injection System -. Decay Heat Removal (DHR) Shutdown Cooling System X 9.3 i System (Residual Heat Removal (RHR) System) Main Steam and Power Conversion Main Steam System, X 10 Systems. Feedwaterand Condensate System. [ Circulating Water System l 1 - Other Heat RemovalSystems .Noneidentified Reactor Coolant Inventory Control Systems 4 - chemical and Volume Control System Same X 9.2 (CVCS)(Charging System) - ECCS See ECCS,above g M 1 m

O C Table 3-1. Summary of Fort Calhoun Systems Covered in this Report (Continued) ? Generic Plant-Specific Report FSAR Section System Name System Name - Section Reference Containment Systems - Containment Same X 5 - Containment Heat Removal Systems - Containment Spray System Same 3.4 6.3 - Ccotainment Fan CoolerSystem Containment Air Recirculation, 3.8 6.4, 9.10 Cooling,and Iodine Removal System P - Containment Normal Ventilation Systems See Containment Air Recirculation, X 9.10 Cooling,and Iodine Removal System, above Combustible Gas ControlSystems Hydrogen Purge System X 9.10 Reactor and Reactivity Control Systems - Reactor Core ' Same X 3 Control Rod System Control Element Drive - X 3 i Mechtnisms(CEDMs) Boration Systems See CVCS, above Instrumentation & Control (I&C) Systems - Reactor Protection System (RPS) Reactor Protective System (RPS). 3.9 7.2 Engineered Safety Feature Actuation Engineered Safeguards Contml - 3.9 7.3 System (ESFAS) System Remote Shutdown System IM Control Panels' 3.9 7.6.4 i -^

- - -. ~.. - n v Table 3-1. Summary of Fort Calhoun Systems Covered in this Report (Continued) Generic. Plant-Specific Report FSAR Section System Name System Name Section Reference Instrumentation & Control (I&C) Systems (continued) - OtherI&CSystems Regulating Systems, X 7.5 Instrumentation Systems X 7.6 ' Support Systems - Class 1E Electric PowerSystem Same 3.5 8.3,8.4 Non-Class 1E Electric Power System Same 3.5 8.2,83 DieselGenerator Auxiliary Systems Same 3.5 8.4 - Component Cooling Water (CCW) Auxiliary Coolant Component 3.6 9.7 System Cooling WaterSystem Service WaterSystem(SWS) Raw Water (RW) System 3.7 9.8 - Other Cooling WaterSystems Turbine Plant Cooling Water X 9.9 System Fue Protection Systems Same X 9.11 - Room Heating Ventilating,and Air-Auxiliary andTurbine Building X 9.10 Conditioning (HVAC) Systems Ventilating Systems, Control Room Air-Conditioning System - Instrument and Service AirSystems Compressed AirSystem X 9.12 Refueling and Spent FuelSystems Same X-9.5,9.6 1:'gg - Radioactive Waste Systems Same X 11 Radiation Protection Systems Same X 11

N p \\ k ) .__....__.F g gp 7... e M LUORICATION COOUNG e w J s ._.r CS PUMP LUmCATiON COOUNG e s e 4 s e e F T... CAC HEAT EXCHANGERS g a r 3 RHR HEAT s. ...r 3... ACCCWS EX N ERS e n w J w J e 'L e s e m e a 6 e r e r MtSSOURt. e ACCCWS-e RWS a gy gm c w J r 1 LPt PUMPS 4L j LUERCATION COCUNG J w J r -+ COumoLRoou ac e J r DIESELGENERATORS Acccws - % coat.re ce ca*.w - > - e J cac-c - -uem cs - c - s,,,, -e e - w w w- ,o ui. u,.e, I. m nas n w s,. m Figure 3-1. Cooling Water Systems Functional Diagram for Fort Calhoun m ..x., m

Fort Calhoun 3.1 REACTOR COOLANT SYSTEM (RCS) (~'N 3.1.1 System Function Q The RCS transfers heat from the reactor core to the secondary coolant system via the steam generators. The RCS pressure boundary also establishes a boundary against the uncontrolled release of radioactive material from the reactor core and pnmary coolant. 3.1.2 System Definition The RCS includes: (a) the reactor vessel, (b) main coolant loops, (c) main coolant pumps, (d) the primary side of the steam generators, (c) pmssurizer, and (f) connected piping out to a suitable isolation valve boundary. Simplified diagrams of the RCS are shown in Figures 3.1-1 and 3.1-2. A summary of data on selected RCS components is presented in Table 3.1 1. 3.1.3 System Goeration During power operation, circulation in the RCS is maintained by four coolant pumps which draw coolant through two steam generators and two main coolant loop vessel discharge lines. The coolant pumps return coolant through four vessel return lines. RCS pressure is maintained within a prescribed band by the combined action of pressurizer heaters and pressurizer spray, RCS coolant inventory is measured by pressurizer water level which is maintained within a prescribed band by the chemical and volume control system (charging system). At power, core heat is transferred to secondary coolant (feedwater) in the steam generators. The heat transfer path to the ultimate heat sink is completed by the main steam and power conversion system and the circulating water system. Following a transient or small LOCA (if RCS inventory is maintained), reactor core heat is still transferred to secondary coolant in the steam generators. Flow in the RCS p is maintained by the main coolant ? umps or by natural circulation. The heat transfer path to V) the ultimate heat sink can be esta 31ished by using the secondary steam relief system (see t Section 3.2) to vent main steam to atmosphere when the power conversion and circulating water systems are not available. If reactor core heat removal by this alternate path is not adequate, the RCS pressure will increase and a heat balance will be established in the RCS by venting steam or reactor coolant to the containment through the pressurizer relief valves, There are two power-operated relief valves and two safety valves on the pressurizer. A continued inability to establish adequate heat transfer to the steam generators will result in a LOCA like condition (i.e., continumg loss of tractor coolant through the pressurizer relief valves). Repeated cycling of these relief valves has resulted in valve failure (i.e., relief valve stuck open). Each power-operated relief valve has an associated motor operated block valve. Following a LOCA, reactor core heat is dumi.ed to the containment as reactor coolant and ECCS makeup water spills from the break. For a short-term period, the containment can act as a heat sink however, the containment spray systems or the containment air cooling systems must operate in order to complete a heat transfer path to the ultimate heat sink (see Sections 3.4 and 3.8). 3.1.4 System Success Criteria The RCS success criteria can be described in terms of LOCA and transient mitigation, as follows: An unmitigatible LOCA is not initiated. If a mitigatible LOCA is initiated, then LOCA mitigating systems are successful. OU 7 12/88

~.. Fort Calhoun If a transient is inititated, then either: RCS integrity is maintained and transient mitigating systems are su::cessful, or ( RCS integrity is not maintained, leading to a LOCA-like condition (i.e. stuck open safety or relief valve, reactor coolant pump seal failure), and LOCA mitigating systems are successful. 3.1.5 Comnonent Information A. RCS 3

1. Volume: 7066 ft, including ressurizer

2. Normal operating pressure: 100 psia B. Pressunzer 3

3 3 1, Volume: 900 ft (500 ft water,400 ft steam) C. Safety Valves (2)

1. Set pressure: 2485 psig

2. Reheicapacity: 200,000 lb/hr each D. Power Operated Relief Valves (2)

1. Set pressure: 2400 psia

2. Relief capacity: 99,000lb/hreach E. Steam Generators

1. Type: Vertical U-Tube

2. Primary side volume: 850 ft3 V

3.1.6 Sunnort Systems and Interfaces A. Motive Power

1. Some pressurizer heaters are Class IE AC loads that can be supplied from the standby diesel generators as described in Section 3.6.

2. The main coolant pumps are supplied from Nca Class IE switchgear.

B. Main Coolant Pump Seal Injection Water System The chemical and volume control system supplies seal water to cool the main coolant pump shaft seals and to maintain a controlled inleakage of seal water into the RCS. Loss of seal water flow may result in RCS leakage through the pump shaft seals which will resemble a small LOCA. W 8 12/88 4 w e y w e -~n---- -a,-

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C O i Table 3.1-1. Ft. Calhoun Reactor Coolant System Data Summary for Selected Components COMPONE.'T ID COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG. TYPE LOC ATION LOAD GRP. RC-101-2 HV RC RC-102-1 SOV RC MCC-3C1 480 EPENRMEAST AC/A RC-102-2 SOV RC MCC-4B1 480 EPENRMWESI AC/B RC-150 MOV RC MCC-381 480 EPENRMEAST AC/A RC-151 MOV RC MCC-4A1 480 EPENRMWEST AC/B k RC-202 NV RC RC-204 NV MECHPENRM RC-347 MOV MECHPENRM MCC-4C2 480 4C2 AC/B RC-348 MOV RC MCC-381 - 480 EPENRMEAST AC/A i i i t i i l' t

Fon CMhoun 3.2 AUXILIARY FEEDWATER (AFW) SYSTEM AND SECONDARY STEAM RELIEF (SSR) SYSTEM 3.2.1 System Function The AFW system provides a source of feedwater to the steam generators to remove heat from the reactor coolant system (RCS) when: (a) the main feedwater system is not available, and (b) RCS 3ressure is too high to permit heat removal by the residual heat removal (RHR) system. "he SSR system provides a steam vent path from the steam generators to the atmosphere, thereby completing the heat transfer path to an ultimate heat sink when the main steam and power conversion systems are not available. Together, the AFW and SSR systems constitute an open loop fluld system that provides for heat transfer from the RCS following transients. 3.2.2 System Definition The AFW system consists of one motor driven pump and one st,:am turbine-driven pump, that draw a suction on the emergency feedwater storage tank (EFST) and supply water to both steam generators when needed. The AFW pump steam turbine drive is supplied from both steam generators and exhausts to atmosphere. Makeup to the EFST is provided from the condensate system. Altemate water sources for the EFST include the demineralized water system, the outside condensate storage tank, and the fire orotection system. The SSR system includes five safety valves on each of the two main steam headers. A steam dump valve also is located in the A main steam header, c'c wnstream of the main steam isolation valve. Simplified drawings of the AFW and SSR systems e showr in Figures 3.2-1 and 3.2 2. A summary of data on selected AFW system components is presented in Table 3.2-1. 3.2.3 System Oneration During normal plant operation, the AFW system is in standby. Both auxiliary feed pumps (FW-6 and FW-10) are automatically started whenever the low water level setpomt is reached in either steam generator; electric power is supplied to the motor driven - pump, FW-6 and the valve admitting steam to the turbine driven pump, FW-10 is opened. All valves in the auxiliary feedwater line from the EFST to the intact steam generator (s) open automaticall if the low water level setpoint has been reached and will open and close. as needed to main ' an acceptable water levelin the steam generator (s). The system also can be remote manually operated from the control room or from a combination of local and remote manual operations from the electrical penetration room. The turbine driven pump, FW-10, requires instrument power forlubrication of the pump. In addition, the steam su The motor driven pump, FW-6,pply valve,1045, fails closed upon loss of control pow is normally aligned to a non Class.1E bus and must be manually aligned to an emergency bus by the operator following a loss of offsite power. The amount of water in the emergency feedwater storage tank is adequate to remove heat for 8 hours. The tank has a capacity at 60,350 gallons and can be resupplied with water from the fire protection system. One of the fire pumps is diesel engine driven 4 and can be used following loss of offsite power. Steam generator dry out time is estimated to be approximately 16 minutes (Ref. 1). The two redundant AFW pumps are available for response with the capability of feeding through two systems of piping. The preferred path is through the auxiliary feedwater piping (valves 1108A, B and 1107A, B). An alternative is to use the main feedwater lines by opening valve 1384. Reactor decay heat is rejected to an ultimate heat ~ sink by venting to atmosphere through the AFW safety valves on each main steam line, b 12 12/88

. = Fort Calhoun Note that the AFW system has two sections of pipe which are single point failures (tank to pump suction and pump discharge to steam generator heat r split). The system also has a component single point failure with manual valve 339. 3.2.4 System Success Crlierla For the decay heat removal function to be successful, both the ARV system and the SSR system must operate successfully. The ARV success criteria are the following (Ref.1): Any one ARV pump can provide adequate flow. Water must be provided from the EFST to the ARV pump suctions Makeup to any one steam generator provides adequate decay heat removal from the reactor coolant system. The SSR system must operate to complete the heat transfer path to the environment. The number of safety valves $at must open for the decay heat removal function is not known, however total system capacity can pass a steam flow equivalent to a reactor power level of 1500 MWt at the secondary safety valve nominal setpoint pressures (i.e.1000 to 1050 psid) (Ref. 2), t 3.2.5 Comnonent Information. A. Steam turbine-driven AFW pump FW 10 l

1. Rated flow: 260 gpm @ 2400 ft head (1040 psid)

2. Rated capacity: 100 %

B. Motor driven AFW pump @FW 6

1. Rated flow: 260 gpm 2400 ft head (1040 psid)

2. Rated capacity: 100 %

C, Emergency feedwater storage tank

1. Capacity: 60,350 gallons D. Secondary steam relief valves

1. Five ASME code safety valves per main steam line (10 total)

)

2. Capacity (total): 6.536 x 10 lb/hr 6

) 3.2.6 Sunnort Systems and Interfaces A. Control Signals

1. Automatic The AFW pumps are automatically actuated based on the following signals:

a. Turbme driven pump FW 10

1) steam generator wide range level

2) differential pressure between two steam generators

3) loss of offsite power

4) trip of main feedwater pumps

b. Motor-driven pump FW 6

1) steam generator wide range level

2) differential pressure between two steam generators

3) trip of main feedwater pumps 13 1248

Fon Calhoun

2. Remote manual The ARV system can be actuated by remote manual means from the

f. )'i main control room

3. Altemate irmote manual ARV pumps can be controlled from an AFW corel panel D. Motive power

1. The ARY motor driven sumpis a non Class IE ACload that can be supplied from the stand sy diesel generators.

2. The ARY valves are Class 1E DC loads that can be supplied from the station batteries. All valves in the normal AFW supply path fall open upon loss of DC power except valve 1045 in the turbine steam supply line to ARY pump RW10.

3. The AFW turbine driven pump is supplied from both main steam headers, upstream of the ma n steam isolation valves.

C. Other

1. Lubrication is piovided locally for pumps, pump motors, and the turbine drive. The lubrication system for the turbine drive requires DC power frorn either the A or B DC bus.

3.2.7 Section 3.2 References

1. NUREO 0635, " Generic Evaluation of Feedwater Transients and Small Break Loss of Coolant Accidents in Combustion Engineering Designed Operating Plants," USNRC, January 1980, p

2. Fort Calhoun Updated FSAR, Section 4.3.4.

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t e Table 3.2-1. Ft. Calhoun Auxiliary Feedwater System Data Summary [ for Selected Components i cot 0PONENT ID COMP. LOCATION POWER SCURCE VO LTAG E POWER SOURCE EMERG. i } TYPE LOCATION LOAD GRP. f j FW-10 TDP AlHCPHM i FW-19 TANK. MSIPENRM f I j FW-6 MDP AlHCPHM BUS-1 A3 4160 SWGHEAST AC/A sea so no ac-2B so ac r i. I I 3 t i 4 I i [ 4 O a I t f T W" = y e i i v J 4 i

. _ ~ Fort Calhoun 3.3 SAFETY INJECTION SYSTEM (SIS) OV 3.3.1 System Functio.n The Safety injection System (SIS) provides for reactor core cooling and coolant inventory control following the loss-of coolant accident (LOCA). The high pressure safety injection (HPSI) subsystem of the SIS that performs the emergency coolant injection and recirculation functions to maintain reactor core coolant inventory and adequate decay heat removal following a small LOCA. The low pressure safety injection (LPSI) subsystem of the SIS perfonns similar functions following a large LOCA. The coolant injection function is performed during a relatively short term penod after LOCA initiation, folle.,,ved by realignment to a recirculation mode of operation to maintain long term, 3ost LOCA core cooling. Heat from the reactor core is transferred to the containment. "he heat transfer path to the ultimate heat sink is completed by the containment spray system (see Section 3.4) or the containment air cooling system (see Section 3.8). 3.3.2 System Definition The Safety injection System consists of the HPSI and LPSI sub>ystems and four safety injection tanks (accumulators). The HPSI subsystem has three pumps that take a suction on the Safety Injection and Refueling Water Tank (SIRWT) during the injection mode of operation, and are realigned to take a suction directly on the containment sump during the recirculation mode of operation. The LPSI subsystem has two p'Ihe HPS umps that ne aligned to either the SIRWT or the containment sump, as described above. LPSI subsystems and the safety injection tanks all inject into the RCS cold legs. Simplified drawings of the high pressure safety injection system are shown in Fi;ures 3.31 and 3.3 2. Interfaces between this system and the RCS are shown in Section

3.. A summary of data on selected high pressure safety injection system components is p

presented in Table 3.31. U 3,3,3 System Ooeration During normal operation, the safety injection system is in standby. Following a LOCA, this system injects borated water into the RCS to increase shutdown margin and to keep the reactor core covered with coolant. The safety injection pumps are started automatically by the Engineered Safety Feature Actuation System (ESFAS See Section 3.9). Borated water is imtially pumped from the SIRW tank to the RCS In addition, the l safety injection actuation signal (SIAS) aligns the charging pumps, in the chemical and volume control system, to take suction from the concentrated bonc acid storage tanks and starts all idle charginj; pumps. Water from the safety injection tanks (SITS) enter the RCS when RCS pressure aups below SIT pressure. The recirculation actuation signal (RAS) automatically switches the pump suction to the containment recirculation inlet when the SIRWT level falls to a preset pomt. At this time, the flow path from the containment sump is opened, the SIRWT flow path is closed and water is recirculated from the sump by the safety injection pumps. Water from the containment sump is also circulated by the containment spray pumps and is cooled by the shutdown cooling heat exchangers. 3,3,4 System Sucress Criteria I LOCA mitigation requires both the emergency coolant injection and emergency coolant recirculation functions to be accomplished. The ECI success criteria for a large LOCA is the following (Ref.1): l { 1 O 18 12/88

t Fort Calhoun 3 of 4 safety injection tanks provide makeup as RCS pressure drops below tank pressure, and j Two high pressure safety injection pumps deliver 75% of their rated flow to the e RCS, and One low pressure safety injection pump deliver 75% of its rated flow to the RCS 1 l If the ECI success criteria is met, then the following large LOCA ECR success criteria will apply (Ref.1): i At least one high pressure safety infection pump is realigned for recirculation and takes a suction on the containment samp and injects into the RCS cold legs. a j Success criteria for a small LOCA is not clearly defined in the FS AR, however, j it should be noted that: The HPSI pump shutoff head is less than RCS normal operating pressure, i therefore, a sinull LOCA must be of sufficient size to cause some RCS ( depressurization, or the RCS must be depressurized by other means if the HPSI aumps are to provide makeup. Options for depressurizing the RCS may nclude: l Opening power-operated relief valves on the pressurizer (two PORVs are available, see Section 3.1) RCS cooldown (i.e. using auxiliary feedwater system, see Section 3.2) The combined capacity of the three positive displacement charging pumps (not j part of the SIS)is 120 gpm (i.e. 40 gpm each). 3.3.5 Comnonent Inrormation A. High pressure safety injection pumps HP 2A, HP 2B, and HP 2C

1. Rated flow: 150 gpm @ 2,800 ft. head (1,214 psid) i

2. Maximum flow: 480 gpm @ 1,200 ft. head (520 psid) 3, Shutoff head: 3,180 ft. (1,378 psid) i

4. Type: multi stage, horizontalcentrifugal B. Low pressure safety injection pumps LP 1 A and LP 1B

1. Rated flow: 1,500 gpm @ 403 ft, head (174 psid) i

2. Shutoff head: 450 ft. (195 psid)

3. Type: Single stage, hosizontal centrifugal C. Safety injection tanks (31 oA, SI 6B, SI 6C, SI 6D)

1. Volume: 1,300 ft3 3

2. Water volume (min): 825 ft '

3. Operating pressure (min): 240 4, Nominal Boron concentration:psig 1,700 ppm D. Safety injection and refueling water tank

1. Capacity: 314,000 gallons.

2. Design Pressure: atmospheric

3. Nominal Boron Concentration: 1,700 ppm (estimated) 19 12/88

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Fort Calhoun E. Shutdown cooling heat exchangers CS 4A and CS-4B I-.

1. Type: shell and tube 6

2. Design duty: 87.5 x 10 BTU /hr 3.3.6 Sumwrt Systems and Interfaces A. Control signals

1. Automatic The safety injection system is automatically actuated by an SIAS signal.

Conditions imtlating an SIAS trip are:

a. Containment high pressure

b. Pressurizer low pressure coincident with pressurizer low water level The tmnsition fmm the injection phase to the recirculation phase is automatic following a RAS signal based on a low water level in the SIR \\VI'.

2. Remote manual An SIAS signal can be initiated by remote manual means from the main con:rol room. The transition from the injection to the recirculation phase of can be accomplished by remote manual actions.

B. Motive' Power

1. The safety injection pumas and motor operated valves are Class lE AC loads that can be supplied from the standby diesel generators.

C. Other

1. Each HPSI pump has mechanical face seals backed u s by a bushing. To arolong seal life, a portion of the pump discharge :s diverted for seal (Qy ubrication. This lubrication flow can be cooled from redundant supplies from the mponent Cooling Water (CCW) and Raw Water (RW) systems (see Sections 3,6 and 3.7).

2. The LPSI pumps can be cooled from redundant supplies from the CCW and RW systems (see Sections 3.6 and 3.7).

3.3.7 Section 3.3 References

1. Fort Calhoun Updated FS AR, Section 6.2.1

\\ 20 12/88

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t t - Table 3.3-1. Ft. Calhoun High Pressure Safety injection System Data Summary ~ for Selected Components I COtsPONENT ID C ORA P. LOCATION POWER SOURCE VOLTAGE POWER SOURCE E BIE R G. i TYPE LOCATION LOAD GRP. [ HP-2A MDP PUMPRMA BUS-183A 480 SWGREAST AC/A [ f HP-2B MDP PUMPRMB BUS-184C 480 SWGRWEST AC/B HP-2C MDP PUMPI54A BUS-183A-4A 480 SWGHEAST AC/AB l f HP-311 MOV RC MCC-301 480 EPENRMEAST AC/A HP-312 MOV RC MCC-4C1 480 EPENRMWEST AC/B [ HP-314 MOV RC MCC-3A1 480 EFENRMEAST AC/A [ HP-315 MOV-RC MCCAA1 480 EPENFWWEST AC/B f f HP-317 MOV RC MCC-3A1 480 EPENRMEAST AC/A HP-318 MOV RC MCC-4A1 480 EPENFWWEST AC/B HP-320 MOV RC MCC-301 480 EPENRMEAST ACIA f HP-321 MOV RC MCC-4C1 400 EPENRMWEST AC/B i f HP-383-3 MOV RC MCC-3A2 480 3A2 AC/A - 3 HP-383-4 MOV-RC MCC-4C2 - 480 4C2 AC/B HP-S8RWT TANK SIRWT j i I - E i l I

l Fort Calhoun l 3,4 CONTAINMENT SPRAY (CS) SYSTEM i 3,4,1 System Function 1 The containment spray system is one of two systems that perform the functions of containment heat removal and containment pressure control following a loss of coolant accident. The Containment Air Cooling (CAC) system is the second system associated with these functions (see Section 3.8). In conjunction with the Safety Injection System (SIS. see Section 3.3), the CS system completes the post LOCA heat transfer path from the reactor core to the ultimate heat sink. I 3,4,2 System Definfilon The containment spray system consists of the Safety injection and Refueling Water Tank (SIRWT), three spray ? umps, two heat exchanges (shutdown cooling heat i exchangers)._ two spray henders ins,de containment, and associated piping, valves, and i instrumentation. The pumps discharge borated water through the two heat exchangers to j the two spray headers and spray nozzles in containment. i Simplified drawings of the containment spray system are shown in Figures l 3.41 and 3.4 2. A summary of data on selected containment spray system components is presented in Table 3.41, 3 3.4.3 System Oneration l During nonnal operation, the containment spray system is in standby. All three spray pumps are started by the safety injection actuation signal (SIAS). The containment l spray actuation signal (CSAS) opens the spray header valves and brings the system to full operation. l Initially, the pumps take suction from the SIRWT. Upor reaching low tank level, the recirculation actuation signal (RAS) is initiated, automatically transferring the containment spra pump suction to the containment recirculation line. The recircu ated i water is cooled b the shutdown heat exchangers prior to being returned into containment atmosphere. Hea is transferred to either the Auxiliary Coolant Component Cooling Water (CCW) system (see Section 3.6), or the Raw Water (RW) system (see Section 3.7). The low pressure safety injection (LPSI) pumps can be aligned to supply the containment spray headers when operating in the recirculation mode. 1 3.4.4 System Success Criteria i lloth the CS and CAC systems have sufficient cooling capacity to independently serform the containment heat removal function. The conta.nment spray system can are met (Ref.1) perform the containment heat removal function if the following conditi ndependently j 1 Two of three containment spray pumps operate and supply water from the SIRWT to the spray headers d unng the injection phase 'Ihe system is realigned for recirculation operation when required Either shutdown cooling heat exchanger provides cooling (CCW or RW available) Partial CS and CAC success criteria may exist, but are not clearly defined in the FSAR. 24 12/88

Fort Calhoun 1 3.4.5 Comnonent Information i A. Containment Spray Pumps CS 3A, CS 3B, and CS 3C

1. Rated flow: 2,000 gpm @ 437 ft head (189 psid)

2. Rated capacity: 50%

3. Type: honzontalceritrifugal i

B. Shutdown cooling heat exchanges CS 4A and CS 4B )

1. Type: shell and tube

2. Design duty: 87.5 x 106 BTU /hr i

3.4.6 Sunnort Svstems and Interfaces A. Control Signals

1. Automatic The containment spray system is automatically actuated by a SlAS signal.

2. Remote manual 1

i All containment spray system compvents can be actuated by remote manual means from the central control room. B. Motive Power

1. i'he CS pumps and motor operated sump suction valves are Class IE AC 1

loads that can be supplied from the standby diesel generators. Redundant 4 i loads are supplied from separate load groups.

2. Hydraulic and pneumatic valves are served by accumulators that allow actuation of the valves following a loss of compressed air. DC power is required.

C. Cooling Water

1. The A'.xiliary Coolant Component Cooling Water (CCW) or the Raw Water (PW) systems provides cooling water to the shutdown cooling heat exchangers (see Sections 3.6 and 3.7).

2. Each CS pump can be cooled from redundant supplies from the CCW and i

RW systems (see Sections 3.6 and 3.7). 3,4,7 Section 3.4 References

1. Fort Calhoun Updated FSAR, Section 6.3.2 25 12/88

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D i Table 3.4-1. Ft. Calhoun Cori.sinment Spray System Data Summary for Selected Components COGBPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. CS^A MDP PUMPRMA BUS-183C 480 SWGREAST ACIA CS-38 MDP PUMPRMB BUS-1848 480 OWGRWEST AC/B [ CS-3C MDP PUMPRMB BUS-1838-48 480 SWGRWEST AC/AB I CS-4A HK SDHXft4A CS-48 HK SDHXRMB i f i f t 6 Sun. I I I ~._

Fort Calhoun I 3.5 ELECTRIC POWER SYSTEM 3.5.1 System Function The electric power system supplies power to various equipment and systems needed for normal operation and/or response to accidents. The onsite Class IE electric power system supports the operation of safety class systems and instnamentation needed to establish and maintain a safe shutdown plant condition following an accident, when the normal electric power sources are not available. 3.5.2 System Definition The onsite Class IE electric power system consists of two 4160/480 VAC and 125 VDC load groups, or dhisions, and four 120 VAC load groups. Each 4160/480 VAC load group consists of a diesel generator and distribution equipment needed to supply key AC electrical loads. Each 125 VAC load group includes a battery, battery chargers, and distribution equipment needed to supply DC loads. Each 120 VAC load group includes an inverter and distribution equipment to supply instrument loads. Simplified one line diagrams of the Class lE electne power system are shown in Figures 3.51 and 3.5 2. A summarv of data on selected electric power system compo.,ents is presented in Table 3.5 1. A partial listing of electrical sources and loads is resented in Table 3.5 2. 3,5.3 System Oncration During normal operation, the Class IE electric power system is supplied by i station service power from the main generator, the 345 kV switchyard or a combination of both. The automatic transfer from this preferred power source to diesel generators is accomplished automatically following a loss of offsite power by opening the normal source circuit breakers and then reenergizing the Class lE portion of the electric power system O from the diesel generators. Following a start command, each diesel generator is designed to reach rated speed and be capable of acce ting loads within 13 seconds. The DC power system normall is supplied through the battery chargers, with the batteries " floating" on the system, malt taining a full charge. Upon loss of AC power, the entire DC load draws from the batteries. The battenes are needed to start the diesel generators following loss of offsite power. The 120 VAC vital buses normally receive power from DC buses through an inverter. The batteries will supply the vital bus inverters on loss of AC power. 3.5.4 System Success Criterin Basic system success criteria for mitijating transients and loss of coolant accidents are defined by front line systems, whLeh then create demands on suppon i systems. Electric power system success criteria are defined as follows, without taking credit for cross ties that may exist between independent load groups: Each Class IE DC load group is supplied initially from its respective battery (also needed for diesel starung) Each Class IE AC load group is isolated from the non Class IE system and is supplied from its respective emergency power source (l.c. diesel generator). Power distribution paths to essennal loads are intact Power to the battery chargers is restored before the batteries are exhausted 29 12/88-4 e -r, -- w m y-8 >~-- --- .rw-------,-e,,... ,m- .,.n.,v.,n..--, g -,,=.m ,,-c., .,-,cw e ,,,,e--, -v> e,n.---- ,y +w..--we' e~ r vn,-% 1

Fort Calhoun 3.5.5 Comnonent Information A. Standby diesel generators (2) ,i

1. Maximum continuous rating: 2402 kW

2. 30-tmnute rating: 2853 kW

3. Rated voltage: 4160 VAC

4. Manufacturer: General Motors B. Batteries (2)

1. Type: Lead calcium

2. Rated voltage: 125 VDC

3. Cells: 60 4 Capacity: 8 hours of operation with design loads 3.5.6 Suonort Systems and Interfaces A. Control Signals

1. Automatic The standby diesel generators are automatically started based on:

Loss of voltage to the normal bus Containment Intemal pressure high Reactor coolant pressure low Time delay undervoltage on the normal bus

2. Remote manual The diesel generators can be staned, and many distribution circuit breakers can be operated from the main contrt>l room.

B. Diesel Generator' Auxiliary Systems

1. Diesel Cooling System

/n') The cooling system for each engine is completely integral and requires no V outside cooling water source.

2. Diesel Starting System The air starting system for each diesel is capable of five start attempts without requiring AC power to recharge the starting air accumulators using att compressors.

3. Diesel Fuel Oil Transfer and Storage System A 300 gallon " day tank" supplies the relatively short term fuel needs of each diesel. The day tanks must be replenished from a common 18,000 gallon storage tank to maintain an uninterrupted supply of fuel to the diesel.

Onsite fuel is sufficient for seven days.

4. Diesel Lubrication System Each diesel generator has its own lubrication system.

5. Combustion AirIntake and Exhaust System This system supplies fresh air to the diesel intake, and directs the diesel exhaust outside of the diesel building.

4

6. Diesel Rt. xn Ventilation System Details of the diesel room ventilation system are not known.

C. Switchgear Roons and Battery Room Ventilation Systems These systems ma ntain acce ) table environmental conditions in the switchgear and battery rooms, ed may x needed for long term o power system. Detal;s cf these systems are not known.peration of the Electr 0 ( 30 12/88

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1. ND

~ ~~ PN A PN B ~ ~ ~ N N N 4 ll Il 11 [ 1ro vAc huS A l l 120 vAc euS C l l t a0 V AC DU6 0 l l 170 VAc tuS 8 l l 11 h h ll ll h h ll i l Bus At ] [ Bus ci l l pus 01 l l Bus si l 11 11 um isoLAtow ... isounow c-6 TRANMORMEM .==, =,==i 1RANSFOnMER 120/1to 120/130 l ausi l I ous e -1 ll II l ova t A l- [ sus :4 l-Figure 3.5 2. Fort Calhoun 125 VDC and 120 VAC Electric Power Distribution System [\\ 32 12/88

r r Table 3.5-1. Ft. Calhoun Electric Power System Data Summary for Selected Components l l COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. BAIT-1 BATT BAIRM1 125 DGA BAIT-2 BATT BATRM2 125 DOB BC1 BC SWGREAST MCC-381 480 EPENRMEAST A':/A BC2 BC SWGRWEST MCP-4A1 400 EFENRMWEST ACB BC3 BC SWGRVEST MCC-3C1 480 EPENRMEAST AQA BUS-1A3 BUS SWGREAST EP-DG1 4160 DGRM1 AQA BUS-1A4 BUS SWGRWEST EP-DG2 4160 DGRM2 AQB BUS-183A BUS SWGREAST EP-3A 480 SWGREAST AC/A BUS-183A-4A BUS SWGREAST BUS-183A 480 SWGREAST AQAB BUS-183A-4A BUS SWGREAST BUS-184A 480 SWGRVEST AQAB BUS-1838 (BUS SWGREAST EP-38 480 SWGREAST AC/A g BUS-1838-48 BUS SWGRVEST BUS-1838 480 SWGREAST AC/AB BUS-1838-48 BUS SWGRVEST BUS-1848 480 ' SWGRWEST l AC/AB BUS-183C BUS SWGREAST EP-3C 480 SWGREAST AQA BUS-183C-4C BUS SWGREAST BUS-183C 480 SWGREAST AQAB BUS-183C-4C BUS SWGREAST BUS-184C 480 SWGRWEST AQAB BUS-184A BUS SWGRWEST EP-4A 480 SWGHWEST ACB BUS-1848 BUS SWGRVEST EP-48 480 SWGRVESI AC/B BUS-184C BUS SWGHWEST EP-4C 480 SWGRWEST AC/B DC-BUS-1 BUS SWGREAST BATT-1 125 BATRM1 DOA DC-BUS-1 BUS SWGREAST BC1 125 SWGREAST DOA DC-BUS-1 BUS SWGREAST BC3 125 SWGRWEST DOA DC-BUS-2 BUS SWGRWEST BATT-2 125 BATRM? DOB DC-BUS-2 BUS SWGRWEST BC2 125 SWGRWEST DOB h DC-BUS-2 BUS SWGRWEST BC3 125 SWGRWEST DC/B EP-1 A3 CB SWGREAST EP-1 A4 CB SWGRVEST EP-3A TRAN SWGREAST BUS-1A3 4160 SWGREAST AQA EP-38 1RAN SWGREAST BUS-1 A3 4160 SWGREAST AQA

i ' Table 3.5-1. Ft. Calhoun Electric Power System Data Summary i for Selected Components (Continued) } COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE. POWER SOURCE EMERG. [ ]' TYPE LOCATION LDAD GRP. EP-3C TRAN SWGREAST BUS-1A3 4160 SWGREAST AQA t 4 EP-4A TRAN SWGRWEST BUS-1 A4 4160 SWGRWEST ACB EP-48 TRAN SWGRWEST BUS-1 A4 4160 SWGRWEST ACB EP-4C TRAN SWGRWEST BUS-1 A4 4160 SWGRWEST AOB EP-DG1 DG DGN1 4160 AC/A i EP-DG2 DG DG W2 4160 ACB { E3A1 MCC. EPENRMEAST BUS-183A 480 SWGREAST AQA 1 MCC-3A2 MCC 3A2 BUS-183A 480 SWGREAST AQA i MCC-381 MCC-EPENRMEAST BUS-1838 480 SWGREAST AQA j j MCC-3C1 MCC EPENRMEAST BUS-183C 480 SWGREAST AGA i l MCC-4A1 MCC EPENRMWEST BUS-184A 480 SWGRWEST AC/B i w MCC-481 WCC EPENRMWEST BUS-1848 480 S N _ST ACB u MCC-4C1 MCC EPENRMWEST BUS-184C 480 SWGRWEST ACB r MCC-4C2 MCC 4C2' BUS-184C 480 SWGRWEST l AC/B 1,- s O ~ i i 4 i kE r f I t

TADLE 3.$4. PAATIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT FORT CALHOUN PDAER VOLTAGE ETARG POW E R SOuRO C LOAD LCAD COMP COMPONENT EOUACf LOAD gap t OC ATION SYSTEM COMPONENTID TYPE LOCATION LATTt 126 DC A BATRMt EP DC BUS 1 BUS SWGREAS T bATTi til DC. A DATRMI FW DC DVS1 BUS SWGREAS F bATT2 126 DGB DATkM2 EP DC buk2 Dv5 SWGRWEST BATT 2 126 DC-D BAT RM2 FW DC bv42 BUS SWGR A E ST DC1 116 DC. A SWGREAST EP DCBUSt BUS SHGREAST 002 126 DC B SWGRWEST EP DCDUS2 BUS SWGRWEST bC3 126 DC A SWGRWEST EP DCDVS1 BUS SWGREAST bC3 126 00 0 SW57IWEST EP DC DV42 DVS SWGRWE F Dub 1 A3 4160 AC/A SWGREAST EP EP 3A TRAN SWGREAST ~ BULI A3 4160 ACiA SWGREAST EP EP 38 TRAN SWGREAST buk t A3 4160 AC/A $WGRF.AST EP EP40 TRAN SWGREAST DVSo A3 4160 AC/A SWGREAST FW FW4 MDP A:RCPRM lubiA3 4160 AceA SWGREAST RW E 10A MDP RWPMAM DLb t As 4160 AC/A SWGREAST RW AC 10C MDP RWPMRM BVS t A4 4160 ACT SWGRWEST EP EP 4A TFMN SWGRWEST O,U 4 BUS i A4 4160 AC/B SWGRWE ST EP EP 40 TRAN SWGRWEST DVS tA4 di60 AC/B SWGRWEST EP EP 4C TRAN SWGRWl3 I BUS 1 A4 4160 AC/D SWGRWEST RW AC.108 MDP RWPMAM bvS 1A4 4160 AC/D SWGRWEST RW ,AC100 MDP RWPMHM BUS tB3A 480 AC, AB SWGREAST EP BUS lB3A 4A BUS SWGREAST DvS 103A 480 AC/A SWGREAST EP MCC-3Al MCC EPENRMEAST BUS 1B3A 480 ACIA SWGREAST EP McC4A2 IM 3A2 BUSIB3A 460 AC/A SWGREAST HP hP 2A MDP PVMPRMA BUStB3A 480 AC/A SWGREAST HP HP 2A MDP PUMPFiMA BubtB3A 460 AC/A SWGREAST VA VA4A FAN AG DVS tB3A 4A 480 AC/AB SWGREAST HP HP 2C MDP PVMPRMA BUS 1B3A 4A 480 AC/AB SWGREAST HP HP 20 MDP PUMPRMA BUS 1638 480 AC< A SWGREAST AC AC4A MDP VENTAM i BUS 183B 480 AC/AB SWGREAST EP BU S-183 B-4 B BUS SWGRWEST BUS 1830 480 AC/A SWGREAST EP MCC4BI WC EPENRMEAST BUSlb3040 480 AC/AB SWGRWEST CS CS4C MDP PUMPRMB O 35 12/88 l i 1

TABLE 3.5 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT FORT CALHOUN (CONTINUED) l POWER YOLTAGE EMERG POWE R Sov40E LOAD LOAD COMP COMPONENT SOUACE LOAD GAD LOCATION svSTEM COMDONENT 10 TYPE LOCAT104 Bus 1930 40 460 AC< AB SWGRWEST VA VA 70 FAN N BUS 163C 460 AC/A SWGREAST CS CS3A MDP PUMPRMA BuSlDC 460 ACi A B SWGREAST EP BUS 1B3C 4C BVS SWGREAST Bv5tB3C 460 AC/A SWGREAST EP MCC-3C1 WC EPENRMEAST BUStB3C4C 480 AC, AB SWGREAST AC AC 3C --~MDP VENTRM BVS 1B3C 4C 460 AC AB SWGREAST VA VA 7C FAN N ~ BUS lb4A 480 ACiB SWGRWEST AC AC 30 MDP VENTRM BUS 104A 480 AC/AB SWGRWEST EP BUS 1B3A 4A BUS SWGREAST BUS 1B4A 460 AC, B SWGRWEST EP MCC-4 A t WC EPENAMWEST BVS1B40 460 AC,0 SWGRWEST CS CS3B MOP PvMPRMB Bv51B4B 480 AC/AB SWGRWEST EP BUS 1B3840 BUS SWORWEST BUS 184B 480 AC/B SWGRWEST EP MCC-4 B I WC EPENAMWEST BUSIB4C 460 AC/AB SWGRWEST EP BUS 1B3C4C BUS SWGREAST EvS184C 480 AC/B SWGRWEST EP MCC-4C1 MCC EPENRMWEST BUStB4C 480 AC/B SWGRWEST EP MCC 4C2 WC 4C2 i BUStB4C 480 AC/B SWGRWEST HP HP 28 MDP PUMPRMB BUS 104C 480 AC/D SWGRWEST HP HP 2B MDP PUMPRMB BU S-l B4 C 480 ACtB SWGRWEST VA VA 3B FAN FC Eo 3A 480 AC<A SWGREAST EP BUS 183A BUS SWGREAST EP 38 480 AC/A SWGREAST EP BUStB3B BUS SWGREAST EP 3C 480 XC/A SWGREAST EP BUS 1B3C BUS SWGREAST E P.4 A 480 ACu B SWGRWEST EP BUS 1B44 BUS SWGRWEST EP 4B 480 AC/B - SWGRWEST EP BUS 1648 BUS SWGRWEST E F-4 C 460 AC/B SWGRWEST EP BUSIB4C BUS SWGRWEST EP DGl 4160 AC/A DGAM) EP BUS 1 A3 BUS SWGREAST EP DG2 4t60 AC< B DGRM2 EP BUSIA4 BUS SWGRWEST MCC 3Al 460 AC/A EPENRMEAST HP HP 314 MOV N MCC3Al 480 AC/A EPENRMEAST HP HP-314 MOV N MCC 3At 480 AC/A EPENRMEAST HP HP 317 MOV FC MCC3At 480 ACIA EPENRMEAST HP HP 317 MOV N MCC 3A2 480 ACIA 3A2 CS CS383 3 MOV AC ( 36 12/88

TABLE 3.5 2. PARTlAL LISTING OF ELECTRICAL SOURCES AND LOADS AT FORT CALHOUN (CONTINUED) POWER VOLTAGE EMEhG POWE R SovRCE LOAD LOAD COMP COMPONENT SOURCE (OAD G AD LOCATION SYSTEM COMDONENTID TYPE t,0 CATION MCC 3A2 480 AC/A 3A2 MP MP 383 3 MOV FC MCC 3BI 480 ACs A EPENRMEAST EP BC1 BC SWGREAST MCC 381 480 AC. A EPENkMEAST MP MP 311 MOV N MCC481 480 AC A EFENAMEAST MP MP 311 MOV N ~ MCC 3Bt 460 AC< A EPENRMEAST HP HP720 MOV FC MCC-381 480 AC. A EPENRMEAST HP e' 320 MOV N MCC-381 460 AC/A EPENRMEAST RCS RC 160 MOV FC MCC 381 480 AC/A EPENRMEAST RCS 7 448 MOV FC MCC4C1 480 AC/A EPENRMEAST EP 'BC3 BC SWGRWEST MCC3C1 480 AC/A EPENAMEAST RCS RC 1021 SOY FC MCC 4A1 480 AC/B EPENRMWEST EP BC2 BC SWGRWEST MCC4A1 480 AC. B EPENRMWEST HP HP 316 MOV FC MCC 4A1 440 AC/B EPENAMWEST HP HP 315 MOV FC MCC 4A1 460 AC/B EPENAMWEST HP HP 318 MOV FC MCC 4A1 480 AC/B EPENRMWEST HP HP 318 MOV N MCC 4A1 480 AC/D ESENRMWEST ACS RC 161 MOV FC MCC 481 480 AC/B EPENRMWEST RCS AC-102 2 SOV N MCC 4C1 480 AC/B EPENAMWEST HP HP 312 MOV FC MCC4C1 480 AC/B EPENRMWEST HP HP 312 MOV N MCC4C1 480 AC, B EPENRMWEST HP HP 321 MOV RC M0C 4C1 480 AC/D EPENRMWEST HP HP 321 MOV N MCC4C2 480 AC/B 4C2 CS CS 383-4 MOV FC MCC4C2 480 AC/B 4C2 HP HP 383-4 MOV N MCC-4 C2 480 AC/B 402 RCS RC447 MOV MECHPENRM i l \\ 37 12/88

Fort Calhoun 3.6 AUXILIARY COOLANT COMPONENT COOLING WATER (CCW) SYSTEM 2 3.6.1 System Function The CCW is designed to cool components carrying radioactive or potentlally radioactive fluids. It also serves as a cooling medium for the containment air coolers and the control room air conditioning equipment. The system provides a monitored intemiediate cooling loop between those fluids and the raw water system which transfers the heat to the ultimate heat sink (see Section 3.7). 3.6.2 System Definition The system is a closed loop consisting of three motor driven circulating pumps, four heat exchangers, a surge tank, valves, piping, instrumentation and controls. The systems which are supported by the CCW include the following: Safety injection / system pump coolin,; Containment spray system pump coo ing Containment air cooling system heat exchanger cooling Shutdown heat exchanger cooling Letdown heat exchanger Reactor coolant pump lube oil coolers Spent fuel pool heat exchangers Charging pump lube oil coolers Simplified drawings of the auxiliary coolant component cooling water system are shown in Figures 3.61 and 3.6.-2. A summary of the data on selected CCW O components is presented in Table 3.61. Note that the plant refers to this system as Q auxiliary coolant (AC) as well as CCW, 3.6.3 System Ooeration During normal operation, one of three CCW pumps and three of four CCW heat exchangers are in service. One pump is in continuous service, while the other two are kept at ready standby. Both standby pumps automatically start in the event that the pump in service trips off. Make up to the CCW is pumped to the surge tank from the demineralized water system through an automatic valve which is actuated by a level control switch on the surge tank. Flow distribution in the system is monitored in the control room and adjustments are made by remote valve operation. During shutdown cooling, two of three CCW pumps and three of four CCW heat exchangers provide adequate cooling capacity. 3.6.4 System Success Criteria Following a design basis accident (DB A), the following success criteria applies to the CCW system (Ref.1). Two-out-of three CCW pumps operate successfully Three-out-of four CCW heat exchangers are available Raw Water System success (see Section 3.7) Note that the Raw Water System is a redundant cooing water source for most of the components served by the CCW system, therefore the RW system can perform the same function as the CCW. Fmce CCW success is dependent on RW success, the CCW o ( system is actually unnecessary w: der emergency conditions. 38 12/88 l l l

Fort Calhoun 3.6.5 Comnonent Information 6 A. Auxiliary coolant CCW pumps AC-3A, AC 3B, and AC 3C m @ 150 ft head (65 psid)

1. Rated flow: 5400 gy% normal,50% shutdown cooling and DBA t

3. Type: hon,acity:lcentrifugal

2. Rated Cap 100 zonta B. Auxiliary coolant CCW heat exchangers AC 1 A, AC-1B, AC lC, and AClD

1. Type: shell and straight tube

2. Rsted heat removal: 12.1 x 106 Btu /hr normal,134 x 106 Bru/hr DBA

3. Rh:ed capacity: 33%

3.6.6 Sunnort Systems and Interfaces A. Control Signals

1. Automatic i

The three pu ps are automatically started fol!owing a safety injection actuation si nal (SIAS). Non-essential cooling loads are shut off following th SIAS.

2. Remote Manual All CCW components can be manipulated from the central control room.

B. Motive Power

1. The CCW motor driven pumps and motor-operated valves are Class IE loads that can be supplied b the standby diesel generators.

2. Deh ulic and pneumat c valves in the system have accumulators so

( that v ve operations can be perfortned following loss of the compressed air system. DC control poweris still needed. C. Other

1. The CCW heat exchanges are cooled by the Raw Water System (see Section 3.7).

2. The CCW pumps do not require extemal cooling support.

3.6.7 Section 3.6 References

1. Fort Calhoun Update FS AR, Section 9.7.4.3.

l 7 LO 3, -w----s--a-w-ge + --m-,. g w e.i ,.7 f p.y,,. ,,q.m.. ,y e-e+,y, w y g.wm-, v+w-.w1-greg= y g39 i-p-.,yw, y g - wry -y - -w y w w-9,c

OV e-4-$-0-0 a a T,';:*.%?# .=*tlt- "tf*E b' ih. 4- @ O -b x- _,4 4, a-4-5 4 4 yh .=4-4.r. B-4-G-e-4 .=4 4.r. ( *r s a tt t b [M=M) O a... x,,, g

x...

g b a (a-1 a-e .=#*er. a a a @ ~0 ~ ?o ~ ~ .=.e- -e.r. e 8 k 4h: = .= 4 M-- -e.=. e g _e. - 4 070. 40*. ( Figure 3.61. Fort Calhoun Auxillary Coolant Component Cooling Water System (Page 1 of 2) 40 12/68

A*,,;f, .".",f *"J'. Ji"J,'#. (k,M}s x M w NJ' w ctu Al MA*h* x x gy.,. h-4 ___.&]c _ p 3 = __ $~l f-S -_ 4 : _.3 + -__ b $$N& -b ___.a. c _. p g __ g_ (v --_4 $VVV$_a m ( _.3 a $~ -__.& :..f-S 34.__- a-f4 -. & ::q s;.- a-4 -- c ;;. ) 4.--- $~ S ---.s $$N$ a _. 3 '( Figure 3.61. Fort Calhoun Auxillery Coolant Component Cooling Water System (Page 2 Of 2) 41-12/88~ i

l h hk 1 --t 44 At TJ = 7 -a+M- -t1*tk 0' N=$=N; v o -J 'a+M- -W+%L

=-

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.s E,

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J'ana. I c oan. Figure 3.6 2 Fort Calhoun Auxillary Coolant Component Cooling Water System Showing Componen* Locat8ons (Page 1 of 2) 42 12/88 1

/4 7.42,

m.,_

1. 1. fJ"o**.-

J!b*f,'J. - i i _M. F ^v-ik--N' w a i,

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== <~ -M.-m%--N- -u a,,, ov, w % a'+ -m , ~...., b _ % }_. ga.___ i -4.r 4 _.s... ]h= : ' *= A - -- (444y 4: _.. ) 4 ---; s.i1 ui ni - < --+ $ _... )_4--, I N#'** I < __4(;.:,74._.s .hm : -m mi, ?m= .. 1 b;s 1 ,pi[ i s__- 4_ ;;. g._ 1 s . un Mai, i .? uo m ammi l n ) Figure 3.6 2. Fort Oathoun Auxillary Coolant Component Cooling Water System ' showing Component Locations (Page 2 of 2) 43 12/88 ) l . - - ~ - -. - .... - - -.. - -. - -. -. -.l

.m t O Table 3.6-1. Ft. Calhoun Auxiliary Coolant Component Cooling Water System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. AC-3A MDP VENIRM BUS-1838 480 SWGREAST ACTA AC-3B MDP VENTRM BUS-184A 480 SWGRWEST AGE AC-3C MDP VENTRM BUS-183C4C 480 SWGREAST ACiAB i AC-A HK CCHXAB AC-B HK CCHXAB i ~i AC-C HX CCHXRM t AC-D HX CCHXRM l-N e 4 i i 'f f 'I 00 00 I i i 1 i i 4

Fon Calhoun 3.7 RAW WATER (RW) SYSTEM O 3.7.1 System Function The raw water system was designed to provide a cooling medium for the component cooling water system. The heat transferred to the raw water is discharged to the ultimate heat sink (the Missouri River). The raw water system can be aligned to directly cool engineered safeguards equipment that normally is cooled by the CCW system. 3.7.2 System Definition Four raw water pumps are installed in the intake structure pump house to provide screened river water to the CCW heat exchangers. The pump discharge piping is arranged as two headers which are interconnected and valved at the pumps and in the auxiliary buildings. Raw water can be utilized for direct cooling of the following: High pressure injection /mcirealation system pumps lubdcation cooling Containment spray system pumps lubrication cooling Containment air cooling system heat exchanger cooiing Shutdown heat exchanger cooling The RW system can also cool the control room air conditioning units and the low pressure injection pumps lubrication cooling, Simplified drawings of the raw water system are shown in Figures 3.7-1 and 3.7 2. A summary of data on selected RW components is presen:ed in Table 3.71, 3.7.3 System Oneration The system is remotely operable from the control room Normally only one Q RW pump is running during plant operation; during shutdown cooling two raw water Q pumps are in operation. All four pumps are started automatically from the safety injection actuation signal (SIAS). The operator selects two pumps to remain operating and shut down the other two pumps. 3.7,4 System Success criterin Following a design basis accident, two RW putnps are needed to provide the required cooling water flow (Ref.1). 3.7.5 Comnonent Informntion A. Raw water pumps AC-10A, AC-108, AC-10C, and AC-10D

1. Rated flow: 5415 gptn @ l18 ft head normal (51 psid).

3100 gpm @ 144 ft head accident (62 psid)

2. Rated capacity: 100% normal,50% shutdown

3. Type: vertical, mixed flow 3.7.6 Sunnort Svstems nnd Interfaces A. Control Signals

1. Automatic The four pumps are automatically started following a safety injection actuation signal (SIAS).

2. Remote Manual All RW components can be manipulated from the central control room.

O 45 12/88

. Fort Calhoun B. Motive Power

1. The RW motor-driven pumps are Class IE loads that cm be supplied by

/" the standby diesel generators...

2. The hydraulic and pneumatic valves in the system have accumulators so that valve operation can be performed following loss of the compressed air system. DC control power is still needed.

3.7.7 Section 3.7 References

1. Fort Calhoun Updated FSAR, Section 9.8.4 4

I. l i I i i i 1 i 4 i i i ? t i 46 12/88

1 l i "Ed'E,* $EIE c..a-se04. .a m_. J.a t AVEL 4WLawf ox a"a .=x' ox_ ox.. S4 = 4.. s.., = CP-6 g,- b8b ox_ ox... . g== Dx== o .c i.e ..-.S.___ __S.. Ox am

== t ( ac i.o 2 2 R I I E _ _ atom h townvo., antum 2 2 -, s.. z.- cm comune I o I N <=.M h.,A.(. Figure 3.71. Fort Calhoun Flaw Water System (Page 1 of 2)- 4 .47 12/88 4

=== g,. - = = g, ma g C g a a -- h b__. g @.o g a g

.1 a

= %7 w .a. a. -.A A. _. a - P.o g o g a __.A A.. __. = = 3 3 r.a E,a

• ~

--s.... ( ~ ~ ) s....-- E A- &a s.a ET ( *** ) 9 f_S a a 4xyg m m

+ p..>4.

1

1. n.#< "E 1

+ t_.p+

2 2 &a &a-4 =T ("** ) N + S S Ka sa = (

• • )

O" A A sa &a ' ' ~ _.s [-~) s,.___ S' kRRRk La 8 i.- LI* IIII o cp =15 ( -- }-W n 8. (,,h Figure 3.71. Fort Calhoun Raw Water System (Page 2 of 2) 48 12/88

n- --um -.w~.~..~n .-s-+.- ....a.- - -........ _. -. ~. _ _ _.,.. _. -.,. - .. _. ~ - ~.. ~. - - - - - - - - 80' k j I l l SepWAN l l 66"8EE I l A AlmM,. .W L88V ' 'O .P_qT_;c.gd_: ..na A _Atmp LJAAV ..x.I m_ .{... teetu A@LJAm To phuDd? A_us t TAM, 34 M ~ 30 - .914P.S-o p, a.. Mi m. ac iac nw ea'.4 - A@LSM i A A L MAV4 .3... .. gag <- COEANT COEANT 4 AG +4D '] -Q' l ?

1. Atalk

&In d,ahAV T0 584ueel COEANT ' -.8B e >... COCLANT s L m g_ R. _.a.. A_ __m

x. _

1 y _.] somunse 1 j ~rt; O"b f g in e n.6 0e i I c c u sa s I m u I..aceau I 4 -: i....., i a s -i ..r... i . :,4 - vo ow. m.cm. 6stAf LOACs. '. MEAY LQatm (PAQ4 8 F4M 4 i v E st ub ]' l Figure 3.7 2. Fort Calhoun Raw Water System Showing Component Locations (Page 1 of 2) 49 12/88 b .v.- ,.-...-,a ..,-.-w-rn w rwan-- -,.,. .--,,n.--n-,--.,-e,w-e,.me,,- w.,,,

....1 .. m - . g., r- -. ~. 2 S f;it. g__S_- z_ l a_ A_ _._ ~ R. S..4,_,5.... _S. ' f f.== = S_ _ _a_ .fEq. a.- wn ~ JL. A.. _._ S_ _ _S_ .f_5"t.R.. R l A_ R> l ,..r-l I M'** I .=' g. 3-f.s-I g.a s.a -- =W [-- ) -te*== < g a a u. ...n G =? {-,.. ] -se== i gi o 1 4 m 39 [-. p-gg.== i 4: 1 4 o k h a' a-

• * ~

?': o - me+$?- [-.,k-itHJ i s 7 - l u. u. s .s i =+$t- [ -,. ) -it~a= 3 .o o-s, u. - s.a _m _m ime+!?- [---) -!?*=: 2 5-A ....? - =+12 [ -~ ) -22==; a g.....a-4 o -o ;- ' mae.e n hM.... - e'OO.... [ Figure 3.7 2. Fort Calhoun Row Water System Showing Component Loca lons (Page 2 of 2) 50 12/88

t m 1 Table 3.7-1. Ft. Calhoun Raw Water System Data Summary l for Selected Components 1 COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. AC-10A MDP RWPMRM-BUS-1A3 4160 SWGREAST AC/A AC-108 MDP RWPMRM BUS-1 A4 4160 ' SWGRWEST ACIB [ AC-10C MDP RWPMRM BUS-1 A3 4160 SWGREAST AC/A AC-10D MDP RWPMRM BUS-1 A4 4160 SWGRWEST AC/B l [ I 4 4 i I 1 i i t M i - gg i i

Fort Calhoun 3,8 CONTAINMENT AIR COOLING (CAC) SYSTEM 3,8,1 System Function The CAC was designed to remove heat relea' d to containment atmosphere during an accident to the extent necessary to initially mu ain that structure below the design pressure and then reduce the pressure to near atmospheric. The s stem also adsorbs iodine in filter banks and prevents accumulation of hydrogen pockets b circulating air in the containment following a design basis accident (DBA). The cooling capability of the CAC system is redundant to that of the containment spray system (see Section 3.4). 3.8.2 System Definition The CAC system consists of four air handling units, each with its own fan, a common plenum discharge systern, and instrumentation and controls, There are two types of units; two have filtering capacity and the other two have no filtering capacity, Those units with filtering capability have larger now rates than the other units. The CAC cooing units are shown in of Figures 3.61 and 3.7-1 as heat loads for the CCW and RW systems. A summary of data on selected CAC components is presented in Table 3.81 3.8,3 System Oneration During normal operation the CAC air cooling units are running, and cooled air is discharged from the plenum through a duct system to those areas where cooling is required. The system is normally manually operated from the central control room but in the event of a LOCA,it is automatically aligned for the emergency operation. Temperature activated hatches and dampers direct airflow from the fan discharge plenum to distnbute air Q in the containment following a DBA. 3,8.4 System Success Criteria Both the CAC and the CS systems have sufficient cooling capacity to independently perform the containment heat removal function. The CAC systera can independently perform the containment heat removal function if the following conditions are met (Ref.1). Any three fan coolers are operating or both the larger fan coolers are operating Either CCW or RW is providing heat exchanger cooling Partial CS and CAC success criteria may exist but are not clearly defined in the 3,8,5 comnonent Information A. Fans VA-3A and VA 3B

1. Rated flow: 90,000 cfm normal,86,500 cfm accident

2. Type: vane axial B. Fans VA-7C and VA 7D

1. Rated flow: 50,000 cfm normal,52,000 cfm accident

2. Type: vane axial O

52 12/88

Fort Calhoun C. Cooling Units VA 1 A and VA 1B 6

1. Rated heat removal: 140 x 10 Btu /hr accident

2. Rated capacity: 50%

D. Cooling units VA 8A and VA 8B 1, Rated heat removal: 70 x 106 Bru/hr accident

2. Rated capacity: 25%

3.8.6 Sunnort Systems and Interface A. Control Signals

1. Automatic The four CAC fans are automatically actuated a.SIAS signal.

Conditions initiating a SIAS are: Containment high pressure Pressurizerlow pressure 2. Remote Manual All containment air cooling system components can be actuated by remote manual means from tic central control room. B. Motive Power

1. The CAC fans are Class 1E AC loads that can be supplied from the.

standby diesel generators.

2. Dampers in the system are fall safe. They will fail open on loss of control power.

C. Cooling Water

1. The cooling units can be cooled by the CCW or the RW systems (see Sections 3.6 and 3.7).

3.8.7 Section 3.8 References

1. Fort Calhoun Updated FS AR, Secdon 6.4.

4 'b)i 53 12/88

t O C C Table 3.8-1. Ft. Calhoun Containment Air Cooling System Data Summary fOr Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. l TYFE LOCATION LOAD GRP. VA-1 A HX RC p VA-18 - HX RC VA-3A FAN RC BUS-183A 480 SWGREAST AC/A VA-38 FAN RC BUS-184C 480 SWGRWEST AC/B VA-7C FAN RC BUS-183C-4C 480 SWGREAST AC/AB 1 VA-7D FAN RC BUS-1 B38-48 480 SWGRVIEST AC/AB VA-8A HX HC VA-8B HX RC t l 3 t i i~ l-E i t 4

Fort Calhoun 3.9 INSTRUMENTATION-AND CONTROL (I&C) SYSTEMS g r. 3.9.1 System Function The instmmentation and control systems include the Reactor Protection System (RPS), the Engineered Safety Feature Actuation Systems (ESFAS), and systems for the l display of plant information to the operators. A remote shutdown capability is provided to ) ensure that the reactor can be placed in a safe condition in the event that the main control room must be evacuated. The RPS and ESFAS monitor the reactor plant, and alert the operator to take corrective action before s xcified limits are exceeded. The RPS will initiate an automatic reactor trip (scram) to rap dly shutdown the reactor when plant conditions 4 exceed one or more specified limits. The ESFAS will automatically actuate selected safety j systems based on the specific limits or combinations oflimits that are exceeded. i 3.9.2 System Definition The RPS includes t nsor and transmitter units, logic units, and output trip 4 relays that operate reactor trip circuit breakers to cause a reactor scram. The ESFAS includes independent sensor and transmitter units, logic units and relays that interface with the control circuits for the tnany different sets of comynents that can be actuated by the ESFAS. The remote shutdown capability is providec; by the Alternate Shutdown Panel j (ASP). Local control panels also are provided for the auxiliary feedwater system. l 3,9.3 System Ooeration 4 A. RPS The Combustion Engineering RPS has four instrument channels and actuation trains (1,2,3, and 4) RPS potential trips are listed below: High rate-of-change of power High power level Low reactor coolant flow Low steam generator water level Low steam generator pressure 1 High pressurizer pressure i Thermal margin / low pressure Containment ?ressure high Axial power cistribution Asymmetric steam generator transient Loss ofload i Manual i The reactor protection system consists of four trip paths operating through coincidence logic to maintain power to, or remove it from, the control element drive mechanisms. Individual channel trips occur when a measurement reaches a preselected setpoint. The channel trips are combined in multiple two-out-of-4 four logic. Each two out of four logic system provides trip signals to one out-of six logic units, each of which causes a direct trip of the contractors in the AC l supply to the control element drive mechanism (CEDM) clutch power suppliers. t B. ESFAS The ESFAS has four input instrument channels and two output actuation trains. In general, the ESFAS "A" train controls equipment powered from Class IE AC electrical Division A and the ESEAS "B" train controls redundant equipment powered from Division B. An individual component usually receives an i 55 12/88 t _, _ _. _ _ - -, _ _. - _ - -, _, ~.,. -- - _ _._. _ _. m.. -, ..,-,._,.-.y

Fort Calhoun = actuation s'ignal from only one ESFAS train. The ESFAS generates the following signals: (1) auto start of the diesel generators, (2) sequential starting O, of engineered safeguards equipment, (3) safety injection actuation signal (SlAS), (4) containment spray actuation signal (CSAS), (5) containment isolation actuation signal (CIAS), (6) ventilauon isolation actuation signal (VIAS), (7) recirculation actuation signal (RAS), (8) auxiliary feedwater system start signal, and (9) offsite power low signal (OPLS). The control room operators can manually trip the various ESFAS logic subsystems, Details regarding ESFAS actuation logic are included in the system description for the actuated system. C. Remote Shutdown The Altemate Shutdown Panel (ASP) contains the necessary instrumentation and control equipment to allow the operator to safely briag the reactor to hot shutdown status and maintain that status until sufficient corrective measures can be taken to allow and maintain a cold shutdown. The Alternate Shutdown Panel is located in the auxiliary building electrical penetration room at elevation 1013' (see Section 4). Local controls panels are also,rovided outside the contml room - for the auxiliary feedwater system, diese. ~ generators, control room air conditioning systems, and various other systems.L The-AFW Regulating Panel-4 contains controls for the auxiliary feedwater valves'and the electric motor driven and turbine driven auxiliary feedwater pumps and their associated recirculation = control valves. The panel also contaLns a master transfer switch to transfer-control of the auxiliary feedwater system from the control room to this point. 3.9.4 System succean critt A, RPS The RPS uses hindrance logic (normal = 1, trip = 0) in both the input and /~'N output logic. Therefore, a channel will be in a trip state when input signals are ! Q lost, when control power is lost, or when the channel is temporarily removed from service for testing or maintenance (i.e. the channel has a fall safe failure - mode). A reactor scram will occur upon loss of control power to the RPS. A' ~ reactor scram usually is implemented by the scram circuit breakers which must - open in response to a scram signal. Typically, there are two series scram cimult breakers in the power path to the scram rods. In this case, one of two circuit - breakers must open. Details of the scram system for Fort Calhoun have not been determined. B. ESFAS A single component usually receives a signal from only one ESFAS output train although all swin trains. ESFAS 'j components and both AFW pumps receive signals fmm both1 rains A and B must be available in order to automatically actuate their respective cornponents. ESFAS typically uses hindrance input - logic (normal = 1, trip = 0) and transmission output logic- (normal = 0, trip -- 1). In this case, an input channel will be in a trip state when input signals are lost, when control power is lost, or when the channel is temporarily removed from service for testing or maintenance (i.e. the channel has a fall safe failure - mode). Control power is needed for the ESFAS output channels to send an actuation signal. Note that there may be some ESFAS actuation subsystems that utilize hinderance output logic. For these subsystems, loss of control power will cause system or component actuation, as is the case.with the RPS. Details of the ESFAS system for Fort Calhoun have not been determined. 56 12/88'

i Fort Calhoun C. Manually.Irdtiated Protective Actions - When reasonable time is available, certain protective actions may be performed operating indm, plant personnel. The control room operators r.re capable o manually by ( dual components using normal control circuitry, or operating groups of components by manually tripping the RPS or an ESFAS subsystem. The control room operators also may send qualified persons into the plant to operate components locally or fmm some other remote control location (i.e., the remote shutdown panel or a motor control center) To make these judgments, data on key plant parameters must be available to the operators. 3.9,5 Sunnort Systems and Interfaces A Control Power

l. RPS The RPS is powered from the four separate independent instrument 120V AC buses as defined in Section 3.6.

2, ESFAS The ESFAS input instrument channels most likely are powered from 120 VAC instrument buses, The ESFAS Train A and B output logic is powered - from the 125 VDC system. 3.9.6 Section 3.9 References

1. Fort Calhoun Updated FS AR, Section 7,6.4 V

57 12/88

Fort Calhoun (~ 4. PLANT INFORMATION 4,1 SITE AND BUILDING

SUMMARY

The Fort Calhoun Po'ver Station is located on a 660 acre site on the west bank of the Missouri River. A general view of the Fort Calhoun site and vicinity is shown in Figure 41 (from Ref.1). The site is approximately 19 miles north of Omaha, Nebraska. The plant is owned and o rated by the Omaha Pubhc Power District. The principa plant structures are the containment building, the auxiliary building, the turbine a" service building, the technical support center, the maintenance shop, and the intake structure. A site arrangement drawing is shown in Figure 4 2. About 85 percent of the site area is on relatively level ground at an elevation of 1007 feet. The reactor, steam generators, reactor coolant pumps and pressurizer are located in the containment, together with other NSSS componer,ts. Access to the building is via a personnel airlock or an equipment hatch. The reactor auxillaries including waste treatment facilities, certain engineered safeguards components, the central control room, personnel facilities, emergency diesel generators, and fuel handling and storage facilities are located on the auxiliary building. This building surrounds about three fourths of the containment building. The auxiliary bu!! ding houses all piping and electrical feeds to the containment along with all emergency electr : power switchgear. The turbine and service buildings, located east of and next to the auxiliary building, house the turbine generator, condenser, condensate and feedwater pumps, feedwater heaters, other turbine heat cycle components, water treatment facilities, auxiliary boiler and conventional auxillaries such as turbine lube oil conditioning equipment. The main condenser cooling water and raw water pumps are located in the n intake structure located east of and away from the turbine and service building. The ( ) Missouri River is the normal heat sink dunng power operation and also is the uamate heat .U sink for safety-related heat loads. 4.2 FACILITY LAYOUT DRAWINGS Figures 4-3 through 4 9 are simplified building layout drawings for the Fort Calhoun containment, auxiliary building and intake structure. The turbine and service building, maintenance shop, and technical support building are not shown on these drawings Major rooms, stairways, elevators, and doorways are shown in the simplified layout drawings, however, many interior walls have been omitted for clarity. Labels printed in uppercase correspond to the location codes listed in Table 41 and used in the component data listings and system drawings in Section 3. Some additionallabels are included for information and are printed in lowercase type. A listing of components by location is presented in Table 4 2. Components included in Table 4 2 are those found in the system data tables in Section 3, therefore this table is only a partial listing of the components and equipment that are located in a particular room or area of the plant. 4.3 SECTION 4 REFERENCES

1. Heddleson, F. A., " Design Data and Safety Features of Commercial Nuclear Power Plants.", ORNL-NSIC 55, Volume 1, Oak Ridge National Laboratory, Nuclear Safety Information Center, December 1973.

58 1248

~ (*~~ NJ v a- . : p -- g.. = n f-aux f_ 8/ g A L-t ~ a (gy & ay+# a F'" ,hi o e o44 " d ~ ~~~~ of ~ N _ _ - -~~~ ogo % s ;g - f 4' [ ' t - c _~ ~ ~. x sp{,#p s+ - 9 FORT CALHOUM i. v. Emme ' 'y f. __4,,,p""d o ,o,c i _\\ l osscuAnse _N sir, og

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i l l NOA* MISSOURI RIVER 1 ,0 _r . a .... INTAKE o o o o o o o s , o o o o o o o STRUCTURE s ^ ^ ^ ^ ^ ^ n n n n n n n e )( s,( K )( r M M M M M M M M M M M M

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b wrl- + g e m- ,.n..n... n m 4 REACTOR pri! 4 ' I $ CONTAINMENT b)b(ll 3 s s 4 m mymywi? NV ( w> s-x m ,m se. ju, r s N M ,~ 1 v. ,m - fo ' v.. " - - n < n.;g?bh:... x7. u ^h *;5~ ( M ?.3,,, ?D E i Q ^> !,t n 4.~l t. 4 s.#,:.d6, s -s_ 3 < *p'^ qw'i }i:Q. )( (f/[%.w:%jd./," Mt. gp gg b j M ( ( x 3 M M L2 %) LJ t.1 L2 L2 LA LJ L2 LJ LA LJ 2 L} n n n n n n n n n n n n n C e Figurs 4 2. Fort Calhoun Plot Plan \\ 60 12/88

... ~... _. _ _ _ _. _ NORTH g O I SRTPM Tendon Gallery PUMPRMB U E5 as sa ii 3 U PUMPRMA l .1 J Figure 4 3. Fort Calhoun Auxiliary Building & Containment Sub-basement (Elevation 97.1') 61 12/88 \\ l ._=....~,-.,..--.._...._J

I i i , NORTH k. EFWTD EFW mci Pump Pump Room d i Removable AlRCPRM Concrete BlocA Wall Removable concrete gU h CCHXRM block wan k c O O CCHXA8 g% Penetration. i SDHXRMg ai / Gas Waste / Treatment SDHXRMA / g g C 5 9, OB' OOL t ( t Liquid W,este U Treatment v nO O 'DHxa" %.n wmmU . Galery O t c.2 ~ O O O^ SPHXRM u% 0UE WHPVVRM

9-j Spenti Fuei

/ 2 4 ;-- Fuel Canal p @ ("

• Pool
• CHPMRM

= '+': ' D gj r CORR 4 .s O 'n l Figure 4 4. Fort Calhoun Auxiliary Building & Containment O Basement (Elevation 989') 62 12/88

.. ~ ~. _ -.... ~. NORTH O C CC O s. SWOREAST BATRM1 Fu 4 0 BATRM T, U ENRMEASTgQ 4 SWORWEST .., b--C Vault O h EPENRMWEST 1 CORR 26 3 oonut sonut Alternate Shutdown Personnet Panel OMf O () Alriock Ventlab.on : PPENRW -C h Equipment 4 Hatch RC ( O U ampa Room S O \\ 'i ocker Room J O o Valve Room g C ' 'M ' k Bone Acid j Spent i Storage New "' Fuel, Fuel O

Pool, Storage _.

WEVRM CORR 26 m O

• O

= o In-O l ~ Volume Control Tank Figure 4 5. Fort Calhoun Auxillary Building & Containment Ground Floor (Elevation 1007,) o

-. =.. , NORTH C CSR VENTRM RC O D less;, W leede 2 uses5 Rool Door u i. innd ' 4 Fuel itg$ys ' Pool n': Primary Water ,,p=tw 7j%n - Storage G 6 1 i 1 Figure 4 6. Fort Calhoun Auxillary Building & Containment O Intermediate Floor (Elevation 1025') 64 12/88 i i --w. -. ,y .,,,., + -. - - - -, y --,e,.,_ ,,,-..-r, s r-v

mRTH e U 0 0 r Request () $'o'o""m' P'4TPENRM CR o.nem Computer Room D 4a"Q Q N \\.6 8;c RC "'R$6) l [ y?h?3f l vent ovets l (Up tvu Roof) O \\ \\j LaJder leads to Rool Door j I fn m a i / TLSF Jo as - l l 1 ) 1 Figure 4 7. Fort Calhoun Auxiliary Building & Containment g Operating Floor (Elevation 103S') s 65 1U88 i

NORTH l 1 Roof' i ~ Elev.10571 l-e e .[ Root

• a1 p

'~T Access, 4 Hatch 51 ._Y, E-{ t .. s i - i3N ' RC i u f ~ x l .'. ~ - .l-p 'V' ent Ducts 1

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x ~ s s 4AccessR 9: Hatch ' m f3\\'s -~ f W. e y e ~. we,as:ua,.. ~ s s. J 1* RW J' C'. ";t ' 1 u .m $U ? Elev. above 1057i@ "O !;ip > < l , s E.M . :me, - j s s p-q. $m s d 3 'l# .j j s % V Figure 4-8. Fort Calhoun Auxiliary Building & Containment (Elevation 1057') 66 12/88

1 l , NORTH j C O 0 1 EU RWPMPRM EE DE u i i ( (l w ELEVATION 10076* L(.] ELEVATION 9934' Note: RWPMPRM is entered from door at 10076* elevation I \\ Sluice t. Gate N

bO

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/ 4 f:f, Circutaing Vater Pumps ( U Circulating - Water Pumpe D M. Eu uM VATION 985 ELEVAT10N 974' 8* // ( Figure 4 9. Fort Calhoun intake Structure 67 12/83

Table 41. Definition of Fort Calhoun Building and i Location Codes Codes Descrintions 1. 3A2 Motor Control Center #3A2, located on the 989' elevation of the Auxiliary Building 2. 4C2 Motor Control Center #4C2, located on the 989' elevation of the Auxiliary Building 3. AIRCPRM Air Compressor Room, located on the 989' elevation of the Auxiliary Building - east side - 4. BATRM1 Battery Room #1, located on the 1011' elevation of the Auxiliary Building - northeast corner 5. BATRM2 Battery Room #2, located on the 1011' elevation of the Auxiliary Building - northeast comer 6. CCHXAB Component Cooling Heat Exchanger Room, located on the 989' ' elevation of the Auxiliary Building east side - contains Component Cooling Heat Exchangers lA and IB 7. CCHXRM-Compon:nt Cooling Heat Exchanger Room, located on the 989' O elevation of the Auxiliary Building - east side - contains Q Component Cooling Heat Exchangers 1C and ID l l 8. CHPMRM : Charging Pump Room, located on the 989' elevation of the Auxiliary Building - northwest corner 9. CORR 26 Corridor #26, located on the 1007' elevation of the Auxiliary Building

10. CORR 4 Corridor #4. located on thc 939' of the Auxiliary Building

11. CR Control Room, located on the 1036' elevation of the Auxiliary Building

12. CSR Cable Spreading Room, located on the 1025' elevation in the Auxiliary Building northeast corner

13. DORM 1 Diesel Generator Room #1, located on the 1007' elevation of the Auxiliary Building - south side

14. DGRM2 Diesel Generator Rootn #2, located on the 1007' elevation of the Auxiliary Building - south side

15. EPENRMEAST East side of the Electrical Penetration Room, located on the 1013'ekvmion of the Auxiliary Building O

68 12/88

. 1 i Table 41. Definition-of Fort Calhoun Building and-Location Codes- (Continued) QuLes Descrintions - t

16. EPENRMWEST Ust side of the Electrical Penetration Room, located on the 1013' elevation of the Auxiliary Building.

17. INTKBLDG Intake Building, located east of the Turbine Room and Service Building

18. LDHXRM Letdown Heat Exchanger Room, located on the 989' elevation of the Auxiliary Building

19. MECHPENRM Mechanical Penetration Room, located on the 989' elevation of the Auxiliary Building -

20. MSTPENRM Main Steam Penetration Room, located on the of the Auxiliary Building-east side

21. PPENRM Pipe Penetration' Room, located on the 1007' elevation of the Auxiliary Building 23, PUMPRMA Pump Room #A, located on the 971' elevation of the Auxiliary.

Building - northwest corner L

24. PUMPRMB Pump P.oom #B, located on the 971' elevation of the Auxiliary.

l . Building - northwest corner

25. RC Reactor Containment

26. RWPMRM-Raw Water Pump Room, located in the Intake Building

27. SDHXRMA Shutdown Heat Exchanger Room #A,-located on the 989' elevation of the Auxillary Building nonheast comer

28. -SDHXRMB Shutdown Heat Exchanger Room.#B, located on the 989'-

elevarion of the Auxiliary Building e northeast comer

29. ' SIRWT Safety injection and Refueling Water Tank, located on the 989' '

of the Aniliary Building - west side '

30. SPHXRM Storage Peol Heat Exchanger Room, located on the 989' elevation of the Auxiliary Building 31, SRTPM Spent Regenerant Tank and Pump Room, located on the 971' elevation of the Auxiliary Building - north side -

32. SWGREAST East side of the Switchgear Room, located on the 1011of the Auxiliary Building 69-

-12/88 ,---e.~,,.i._,r.- e,y ~ r +.,',,w,.- ..f,-.nwreg'-*e t* we g w w - -~'f w+m e e-t 'w e *w e vm'y t

i Table 41. Definition of Fort Calhoun Building and Location Codes (Continued) C,gdg3 Descrintions 3L SWORWEST West side of the Switchgear Room, located on the 1011' clevation of the AuxlEary Building

34. TLSF Top Level of the S sent Fuel Pool. located on th 1038' elevation of the Auxiliary Bu,lding

35. VENTRM Ventilation Room, located on the 1025' elevation of the Auxiliary Building

36. VVRM Valve Room, located on the 989' elevation of the Auxiilary Building northeist corner

37. WEVRM Waste Eva mrator Room, located on the 1007' elevation of the Aaxillary I uilding northwest comer

38. WHPVVRM Waste Hold Up Pump Valve Room, located on the 989' elevation of the Auxiliary Building northwest corner O

l l i O 70 !2/88 l ,-m

____.____-m l TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION l AT FORT CALHOUN LOCATION SYSTEM COMPONENT 10 COMP TYPE 3At EP MCC-3A2 MCC 4C2 EP MCC4C2 WC M DPRM FW FW4 MDP AIRCPRM FW FW 10 TOP BATRMI EP BATT.1 BATT BATRM2 ^ EP BATT 2 BATT CCHAAB AC AC A HK CCHXAB AC AC B HK CCHARM AC AC4 HK CCHxRM AC AC-O HK DGRM) EP EP OGl 00 DGRM2 EP EPCGI 00 EPENRMEAST EP MCC 381 E' EPENRMEAST EP MCCW ) MCC EPENRMEAST EP MCC 3At MCC EPENRMWEST EP MCC 4A1 MCC EPENRMWEST EP MCC4Cl C EPENRMWEST EP MCC 4BI MCC MECHPENRM RCS RC447 MOV MECHPENRM RCS RC 204 NV MSTPENRM FW FW19 TANK PUMPRMA CS CS-3A MDP PUMPRMA HP HP 2A MDP PUMPRMA HP HP 20 MDP PUMPRMA HP HP 26 MDP PUMPRMA HP HP-20 MDP PUMPRMB CS CS4B MDP PUMPRMB CS CS4C MDP PUMPRMB HP HP 2B MDP T'UMPP.MB HP HP 2B - MDP W AC VA 1A HK b 71 12/88

TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATICH AT FORT CALHOUN (CONTINUED). CT V '- LOCATION SYSTEM CCMPONENT 40 COMP TYPE FC AC VA 10 KK N AC VA 6A K4 N AC VA 6B KA N CS CS-3b3 3 MOV FC CS CS-363 4 MOV TC FW PC 2A SG N FW RC 2B SG N HP HP 311 MOV FC HP HP 312 MOV N HP HP 314 MOV' ~ N HP HP 316 EV FC HP HP 317 MOV N HP HP 310 MOV N HP HP 320 IADV i FC HP HP 321 MOV '\\ IM HP HP 363 3 MOV FC HP HP 311 MOV FC HP HP 312 MOV FC HP HP 3td MOV N HP HP 315 MOV RC HP HP 317 MOV FC HP HP 318 MOV FC HP HP 320 MOV FC HP HPM1 MOV N HP HP 383 4 MOV RC RCS RC-348 MOV RC RCS RC 102 2 SOV N RCS RC-150 MOV FC RCS RC 1021 SOV N RCS RC 161 MOV ps FC ES RC-1012 HV U) 72 12/88 I l }j j

TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION AT FORT CALHOUN (CONTINUED). ( LOCATION SYSTEM COMPONENT ID COMP TYPE N MS RM02 NV N RW VATA KK N RW VA6A HK FC RW VA-6B H( RW VA 1B HK N VA VA1A HK N VA VA 3A FAN N VA VA 1b HK N VA VA 30 FAN N VA VA8A HK FC VA VA 7C FAN I N VA VA 8B HK N VA VA 7D FAN RWPMRM RW AC 10A MDP RWPMRM RW AC 108 MDP \\ RWPMRM RW AC 100 MDP RWPMRM RW AC 10D MDP SOHARMA CS C5-4A HK SOHARMB CS C5-45 HK S4RWT HP HP-SIRWT TANK CWGRE.AST EP BUS 1 A3 BUS SWOREAST EP EP1A3 CB SWGREAST EP BUS 1B3A BUS l 5WGREAST EP EP 3A TRAN SWOREAST EP BUS 1B3C BUB SWGREAST EP EP 3C TRAN SWOREAST E! BUS 1B3B BUS SWGREAST EP EP 38 TRAN SWGREAST EP DCBUS1 BUS SWOREAST EP BUS 1830 4C BUS f DJPFAST EP BUS-1830-4C BUS km 73 12/88

_m ] TABLE 4 2. PARTIAL Ll8 TING OF COMPONENTS BY LOCATION AT FORT CALHOUN (CONTINUED). \\ LOCATON SYSIEM COMPONENT 40 COMP TYPE SWGAEAST EP DCBUS1 BUS SWGREAST EP DCBUS1 'C SWGREAST lP BC1 BC SWGREAST EP BUS 183A 4A BUS SWOREAST EP BUS 183A 4A BUS SWGREAST FW DC-BUS 1 BUS SWGRWEST EP BUS 1 A4 BUS SWGRWEST EP EP 1 A4 CB SWGRWEST EP BUS 1B4A BUS SWGRWEST EP E P-4A TRAN SWGRWEST EP BUS 1848 GUS SWORWEST EP EP-48 TRAN SWGRWEST EP BUS 1B4C BUS SWORWEST EP EP.4C TRAN l SWGRWEST EP DC BUS-2 BUS SWORWEST EP B08-1538-45 BUS SWGRWEST EP BUS 1838 4B BUS SWGRWEST EP BC3 BC l SWGRWEST EP D0808 2 BUS j SWORWEST EP DC-BUS-2 BUS SWORWEST EP BC2 BC SWGRWEST FW DC BUS-2 BU5 VENTRM AC AC4A MDP VENTRM AC AC48 MDP VENTRM AC AC40 MDP 74 1148 I ewrv. -s-p ,r,, ,,-nn ,--.n- --,wn e...,,-+r...- e,,.,-m e .s., .,4 +-

l ? 5. BIBLIOGRAPilY FOR FORT CALHOUN POWER STATION

1. El Shamy, F., " Aquatic impacts From Operation of Three Midwestern Nuclear Power Stations: Fort Calhoun Station, Unit No.1, Environmental Appraisal Report" NUREO/CR 2337 Volume 1 Environmental Sciences

& Engineering, Inc., October 1981,

2. NUREG 0635, " Genetic Evaluation of Feedwater Transients and Small Break Loss of Coolant Accidents in Combustion Engineering Designed Operating Plants", Section X 3, " Fort Calhoun Auxiliary Feedwater System", USNRC, January 1980.

' 3. NUREO/CR 0705, " Gamma Dose Measurements at Zion and Fort Calhoun Stations" EO&O Idaho,Inc., April 1979.

4. NUREO/CR 0140, "In Plant Source Term Measurements at Fort Calhoun Station, Unit 1", EO&O Idaho, Inc., August 1978, i

l l l i l i N U 75 - 12/88- -..,..,. =. _, =.. ~. 2.--.-...,, _.___,,.2_.,.- ..,--,-a}}